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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Remembering Charles E. Till
Charles E. Till
Charles E. Till, an ANS member since 1963 and Fellow since 1987, passed away on March 22 at the age of 89. He earned bachelor’s and master’s degrees from the University of Saskatchewan and a Ph.D. in nuclear engineering from Imperial College, University of London. Till initially worked for the Civilian Atomic Power Department of the Canadian General Electric Company, where he was the physicist in charge of the startup of the first prototype CANDU reactor in Canada.
Till joined Argonne National Laboratory in 1963 in the Applied Physics Division, where he worked as an experimentalist in the Fast Critical Experiments program. He then moved to additional positions of increasing responsibility, becoming division director in 1973. Under his leadership, the Applied Physics Division established itself as one of the elite reactor physics organizations in the world. Both the experimental (critical experiments and nuclear data measurements) and nuclear analysis methods work were internationally recognized. Till led Argonne’s participation in the International Nuclear Fuel Cycle Evaluation (INFCE), and he was the lead U.S. delegate to INFCE Working Group 5, Fast Breeders.
Roberto Orsi
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 110-116
Computer Code Abstract | doi.org/10.13182/NSE07-A2716
Articles are hosted by Taylor and Francis Online.
This paper aims to stimulate research and to focus the attention of deterministic radiation transport code developers and users on further methodologies in transport analysis that some recent additions to the code package BOT3P potentially make possible in structured Cartesian or cylindrical mesh grids simulating complex geometries. In particular, BOT3P Version 5.0 can compute the possible area/volume error of material zones due to the stair-cased geometrical representation and automatically correct material densities in order to conserve masses, as described in a previous BOT3P paper published in Volume 154, Number 2 of Nuclear Science and Engineering to which the present one is logically and strictly related. When calculating areas and volumes refinements or when reducing the problem sizes of a voxelized geometry, typical of medical applications, BOT3P generates binary files that store also a fine submesh grid for each coarse cell at material interfaces. These files were originally conceived only for density correction computation and plotting purposes. However, the availability of such cell data intuitively suggests multistep transport analysis approaches that may combine detailed solutions at material interfaces with acceptable problem sizes and computational times. Reaching this appealing target could let deterministic codes based on structured mesh grid successfully deal with any challenging geometry problem. That might be particularly useful in medical and reactor applications.